Tritium Transport Analysis in a 2-MW Liquid-Fueled Molten Salt Experimental Reactor with the Code TMSR-TTAC

doi:10.1080/00295450.2018.1507200

CORC > 上海应用物理研究所 > 中国科学院上海应用物理研究所 > 中科院上海应用物理研究所2011-2017年

	Tritium Transport Analysis in a 2-MW Liquid-Fueled Molten Salt Experimental Reactor with the Code TMSR-TTAC
	Zeng, YS; Liu, WG; Liu, W; Wang, GH; Qian, Y; Qian, N; Wu, XL; Huang, Y; Wu, SW
刊名	NUCLEAR TECHNOLOGY
	2019
卷号	205 期号:4 页码:582—591
关键词	SOLUBILITIES DEUTERIUM HYDROGEN
ISSN号	0029-5450
DOI	10.1080/00295450.2018.1507200
文献子类	期刊论文
英文摘要	In the Thorium-Based Molten Salt Reactor (TMSR), tritium is produced at a high rate, which results in huge dculties regarding tritium control. Tritium distributions in a 2-MW liquid-fueled molten salt experimental reactor (TMSR-LF1) were simulated with the TMSR-Tritium Transport Analysis Code (TTAC) (TMSR-TTAC) that was developed for analysis of tritium behaviors in the TMSR. The simulation for normal operation showed that about 60% of the tritium would permeate through the metal walls of the system, 25% of the tritium was removed by the purge gas system, and 15% of the tritium was absorbed on the core graphite. In addition, the effects on tritium distribution of the chemical-redox potential in fuel salt, the tritium permeation behavior through the metal walls, and various tritium removal methods in the TMSR-LF1 have also been simulated. The simulation results based on those conditions are analyzed in this paper to improve the knowledge of tritium behavior in the TMSR-LF1 and to provide reliable methods and strategies for tritium control in the TMSR system.
语种	英语
内容类型	期刊论文
源URL	[http://ir.sinap.ac.cn/handle/331007/31888]
专题	上海应用物理研究所_中科院上海应用物理研究所2011-2017年
作者单位	Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China
推荐引用方式 GB/T 7714	Zeng, YS,Liu, WG,Liu, W,et al. Tritium Transport Analysis in a 2-MW Liquid-Fueled Molten Salt Experimental Reactor with the Code TMSR-TTAC[J]. NUCLEAR TECHNOLOGY,2019,205(4):582—591.
APA	Zeng, YS.,Liu, WG.,Liu, W.,Wang, GH.,Qian, Y.,...&Wu, SW.(2019).Tritium Transport Analysis in a 2-MW Liquid-Fueled Molten Salt Experimental Reactor with the Code TMSR-TTAC.NUCLEAR TECHNOLOGY,205(4),582—591.
MLA	Zeng, YS,et al."Tritium Transport Analysis in a 2-MW Liquid-Fueled Molten Salt Experimental Reactor with the Code TMSR-TTAC".NUCLEAR TECHNOLOGY 205.4(2019):582—591.